The neutron within the deuteron as a surrogate for neutron-induced reactions
01 Dec 2019-International Journal of Modern Physics E-nuclear Physics (World Scientific Publishing Company)-Vol. 28, Iss: 12, pp 1950109
TL;DR: In this article, the use of neutron poisons in reactions induced by radioactive beams was proposed as a test of theoretical models aiming to relate neutron capture in nuclei with neutron surrogate reactions such as (1)
Abstract: We propose the use of neutron poisons in reactions induced by radioactive beams as a test of theoretical models aiming to relate neutron capture in nuclei with neutron surrogate reactions such as (...
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TL;DR: Eisenbud and Wigner as discussed by the authors discussed the nuclear structure of the atom and the nuclear power system, and showed that it is composed of a set of sub-networks.
Abstract: Nuclear Structure By Leonard Eisenbud and Prof. Eugene P. Wigner. (Investigations in Physics, Vol. 8.) Pp. viii + 128. (Princeton, N.J.: Princeton University Press; London: Oxford University Press, 1958.) 25s. net.
11 citations
TL;DR: In this article, the sensitivity of transfer reactions to the bound state wave functions within a distorted wave Born approximation formalism was investigated using supersymmetric transformations. But the results were limited to the case of O 16 ( d, p ) 17 O and C 12 ( 7 Li, t ) 16 O reactions.
4 citations
26 Jul 2013
TL;DR: In this paper, the authors evaluated the gadolinium-entrapped liposome compound as a neutron capture therapy agent by in vivo experiment on colon-26 tumor-bearing mice.
Abstract: Neutron capture therapy (NCT) is a promising non-invasive cancer therapy approach and some recent NCT research has focused on using compounds containing gadolinium as an alternative to currently used boron-10 considering several advantages that gadolinium offers compared to those of boron. In this study, we evaluated gadolinium-entrapped liposome compound as neutron capture therapy agent by in vivo experiment on colon-26 tumor-bearing mice. Gadolinium compound were injected intravenously via tail vein and allowed to accumulate into tumor site. Tumor samples were taken for quantitative analysis by ICP-MS at 2, 12, and 24 h after gadolinium compound injection. Highest gadolinium concentration was observed at about 2 h after gadolinium compound injection with an average of 40.3 μg/g of wet tumor tissue. We performed neutron irradiation at JRR-4 reactor facility of Japan Atomic Energy Research Institute in Tokaimura with average neutron fluence of 2×10¹² n/cm². The experimental results showed that the tumor growth suppression of gadolinium-injected irradiated group was revealed until about four times higher compared to the control group, and no significant weight loss were observed after treatment suggesting low systemic toxicity of this compound. The gadolinium-entrapped liposome will become one of the candidates for Gd delivery system on NCT.
4 citations
TL;DR: In this paper, a short review of transfer reactions is presented, where the role of the remnant terms, post-prior form equivalence, peripherality of the reaction and sensitivity of the transfer cross sections to the bound state wave functions are discussed.
Abstract: We have recently applied the R-matrix method to transfer reactions in the distorted wave Born approximation (DWBA) framework. In our approach the wave function in the internal region is expanded in terms of Lagrange basis, which provides a fast and efficient way to compute the matrix elements. This paper is a short review of our work on transfer reactions. I discuss applications of our approach by considering the $$^{16}$$
O(d, n)
$$^{17}$$
F and $$^{12}$$
C(
$$^7$$
Li, t)
$$^{16}$$
O reactions, which are specific examples of neutron and $$\alpha $$
transfer, respectively. In particular, I discuss the role of the remnant terms, post-prior form equivalence, peripherality of the reaction and sensitivity of the transfer cross sections to the bound state wave functions. Effects of the remnant terms and of the supersymmetric bound state potentials on the extracted spectroscopic factors are also discussed.
2 citations
TL;DR: In this article, the cross section and transition rate of the He reaction were calculated using a post-form distorted-wave Born approximation in a simple cluster model using a simple model.
Abstract: The $${}^{5}$$
He(
$${}^{3}$$
He,
$${}^{4}$$
He)
$${}^{4}$$
He reaction involving the unstable $${}^{5}$$
He nucleus is a possible process in primordial nucleosynthesis to convert $${}^{3}$$
He into $${}^{4}$$
He in a neutron transfer reaction. Since experimental data for the reaction cross section are not available, a theoretical prediction is needed to estimate the relevance of this process in comparison to other reactions, e.g., $${}^{3}$$
He(
$${}^{2}$$
H,p)
$${}^{4}$$
He or $${}^{3}$$
H(
$${}^{2}$$
H,n)
$${}^{4}$$
He. In this work the cross section and the Maxwellian-averaged transition rate of the $${}^{5}$$
He(
$${}^{3}$$
He,
$${}^{4}$$
He)
$${}^{4}$$
He reaction are calculated using a post-form distorted-wave Born approximation in a simple cluster model. For that purpose the reaction is treated as a genuine process with three particles, $$\text{ n }+{}^{4}\text{ He }+{}^{3}\text{ He }$$
, in the entrance channel proceeding through the $$3/2^{-}$$
resonance in the $$n-{}^{4}$$
He scattering continuum.
2 citations
References
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TL;DR: In this article, a count of the stable and radioactive elements and isotopes is given, and Table I,1 shows that only promethium has not been found in nature, whereas 99 elements are found terrestrially and technetium is found in stars.
Abstract: Man inhabits a universe composed of a great variety of elements and their isotopes. In Table I,1 a count of the stable and radioactive elements and isotopes is listed. Ninety elements are found terrestrially and one more, technetium, is found in stars; only promethium has not been found in nature.
2,951 citations
1,525 citations
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01 Jan 1958
TL;DR: The second edition of the Handbuch der Physik was published in 1904 by Winkelmann et al. as mentioned in this paper, which is an indispensable storehouse of expert knowledge in all branches of the subject, and the need for another edition enables it to be brought once more abreast of the rapidly advancing tide of knowledge.
Abstract: EVERY student of physics will share the satisfaction of the editor of this treatise that a second edition was called for so soon; for he has found it to be an indispensable storehouse of expert knowledge in all branches of the subject, and the need for another edition enables it to be brought once more abreast of the rapidly advancing tide of knowledge.Handbuch der Physik.By Dr. A. Winkelmann. Second Edition. First part of vol. iv., Electricity and Magnetism. 140 figures. Price 12 marks. First part of vol. vi., Optics. 170 figures. Price 14 marks. (Leipzig: Barth, 1904.)
770 citations
"The neutron within the deuteron as ..." refers methods in this paper
...In Figure 1 we show three results for the deuteron nucleon momentum distribution obtained with (a) the Hulthen [31] momentum distribution (dashed line), and the corresponding distributions from the Bonn [32] (solid line) and from the Paris [33] (dotted line) potentials....
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...We will use the Hulthen [31] to calculate the matching function, as displayed in Figure 2....
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...[31] L. Hulthén and M. Sugawara, in Handbuch der Physik, edited by S. Flugge (Springer-Verlag, Berlin, 1957), Vol. 39....
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Book•
16 Jan 2001
TL;DR: In this article, the authors present a detailed overview of the basic physics of neutron nuclear reactions and their application in the context of nuclear power plants, including the following: 1.1 Neutron-Induced Fission Reactions 2.2 Neutral Capture 3.3 Diffusion Kernels and Distributed Sources in a Homogeneous Medium 3.4 Classification of Nuclear Reactors 4.5 Reactor Reactions 5.6 Reactor Safety 6.
Abstract: Preface. Preface to 2nd Edition. PART 1 BASIC REACTOR PHYSICS. 1 Neutron Nuclear Reactions. 1.1 Neutron-Induced Nuclear Fission. 1.2 Neutron Capture. 1.3 Neutron Elastic Scattering. 1.4 Summary of Cross-Section Data. 1.5 Evaluated Nuclear Data Files. 1.6 Elastic Scattering Kinematics. 2 Neutron Chain Fission Reactors. 2.1 Neutron Chain Fission Reactions. 2.2 Criticality. 2.3 Time Dependence of a Neutron Fission Chain Assembly. 2.4 Classification of Nuclear Reactors. 3 Neutron Diffusion Theory. 3.1 Derivation of One-Speed Diffusion Theory. 3.2 Solutions of the Neutron Diffusion Equation in Nonmultiplying Media. 3.3 Diffusion Kernels and Distributed Sources in a Homogeneous Medium. 3.4 Albedo Boundary Condition. 3.5 Neutron Diffusion and Migration Lengths. 3.6 Bare Homogeneous Reactor. 3.7 Reflected Reactor. 3.8 Homogenization of a Heterogeneous Fuel-Moderator Assembly. 3.9 Control Rods. 3.10 Numerical Solution of Diffusion Equation. 3.11 Nodal Approximation. 3.12 Transport Methods. 4 Neutron Energy Distribution. 4.1 Analytical Solutions in an Infinite Medium. 4.2 Multigroup Calculation of Neutron Energy Distribution in an Infinite Medium. 4.3 Resonance Absorption. 4.4 Multigroup Diffusion Theory. 5 Nuclear Reactor Dynamics. 5.1 Delayed Fission Neutrons. 5.2 Point Kinetics Equations. 5.3 Period-Reactivity Relations. 5.4 Approximate Solutions of the Point Neutron Kinetics Equations. 5.5 Delayed Neutron Kernel and Zero-Power Transfer Function. 5.6 Experimental Determination of Neutron Kinetics Parameters. 5.7 Reactivity Feedback. 5.8 Perturbation Theory Evaluation of Reactivity Temperature Coefficients. 5.9 Reactor Stability. 5.10 Measurement of Reactor Transfer Functions. 5.11 Reactor Transients with Feedback. 5.12 Reactor Fast Excursions. 5.13 Numerical Methods. 6 Fuel Burnup. 6.1 Changes in Fuel Composition. 6.2 Samarium and Xenon. 6.3 Fertile-to-Fissile Conversion and Breeding. 6.4 Simple Model of Fuel Depletion. 6.5 Fuel Reprocessing and Recycling. 6.6 Radioactive Waste. 6.7 Burning Surplus Weapons-Grade Uranium and Plutonium. 6.8 Utilization of Uranium Energy Content. 6.9 Transmutation of Spent Nuclear Fuel. 6.10 Closing the Nuclear Fuel Cycle. 7 Nuclear Power Reactors. 7.1 Pressurized Water Reactors. 7.2 Boiling Water Reactors. 7.3 Pressure Tube Heavy Water-Moderated Reactors. 7.4 Pressure Tube Graphite-Moderated Reactors. 7.5 Graphite-Moderated Gas-Cooled Reactors. 7.6 Liquid-Metal Fast Breeder Reactors. 7.7 Other Power Reactors. 7.8 Characteristics of Power Reactors. 7.9 Advanced Generation-III Reactors. 7.10 Advanced Generation-IV Reactors. 7.11 Advanced Sub-critical Reactors. 7.12 Nuclear Reactor Analysis. 7.13 Interaction of Reactor Physics and Reactor Thermal Hydraulics. 8 Reactor Safety. 8.1 Elements of Reactor Safety. 8.2 Reactor Safety Analysis. 8.3 Quantitative Risk Assessment. 8.4 Reactor Accidents. 8.5 Passive Safety. PART 2 ADVANCED REACTOR PHYSICS. 9 Neutron Transport Theory. 9.1 Neutron Transport Equation. 9.2 Integral Transport Theory. 9.3 Collision Probability Methods. 9.4 Interface Current Methods in Slab Geometry. 9.5 Multidimensional Interface Current Methods. 9.6 Spherical Harmonics (PL) Methods in One-Dimensional Geometries. 9.7 Multidimensional Spherical Harmonics (PL) Transport Theory. 9.8 Discrete Ordinates Methods in One-Dimensional Slab Geometry. 9.9 Discrete Ordinates Methods in One-Dimensional Spherical Geometry. 9.10 Multidimensional Discrete Ordinates Methods. 9.11 Even-Parity Transport Formulation. 9.12 Monte Carlo Methods. 10 Neutron Slowing Down. 10.1 Elastic Scattering Transfer Function. 10.2 P1 and B1 Slowing-Down Equations. 10.3 Diffusion Theory. 10.4 Continuous Slowing-Down Theory. 10.5 Multigroup Discrete Ordinates Transport Theory. 11 Resonance Absorption. 11.1 Resonance Cross Sections. 11.2 Widely Spaced Single-Level Resonances in a Heterogeneous Fuel-Moderator Lattice. 11.3 Calculation of First-Flight Escape Probabilities. 11.4 Unresolved Resonances. 11.5 Multiband Treatment of Spatially Dependent Self-Shielding. 11.6 Resonance Cross-Section Representations. 12 Neutron Thermalization. 12.1 Double Differential Scattering Cross Section for Thermal Neutrons. 12.2 Neutron Scattering from a Monatomic Maxwellian Gas. 12.3 Thermal Neutron Scattering from Bound Nuclei. 12.4 Calculation of the Thermal Neutron Spectra in Homogeneous Media. 12.5 Calculation of Thermal Neutron Energy Spectra in Heterogeneous Lattices. 12.6 Pulsed Neutron Thermalization. 13 Perturbation and Variational Methods. 13.1 Perturbation Theory Reactivity Estimate. 13.2 Adjoint Operators and Importance Function. 13.3 Variational/Generalized Perturbation Reactivity Estimate. 13.4 Variational/Generalized Perturbation Theory Estimates of Reaction Rate Ratios in Critical Reactors. 13.5 Variational/Generalized Perturbation Theory Estimates of Reaction Rates. 13.6 Variational Theory. 13.7 Variational Estimate of Intermediate Resonance Integral. 13.8 Heterogeneity Reactivity Effects. 13.9 Variational Derivation of Approximate Equations. 13.10 Variational Even-Parity Transport Approximations. 13.11 Boundary Perturbation Theory. 14 Homogenization. 14.1 Equivalent Homogenized Cross Sections. 14.2 ABH Collision Probability Method. 14.3 Blackness Theory. 14.4 Fuel Assembly Transport Calculations. 14.5 Homogenization Theory. 14.6 Equivalence Homogenization Theory. 14.7 Multiscale Expansion Homogenization Theory. 14.8 Flux Detail Reconstruction. 15 Nodal and Synthesis Methods. 15.1 General Nodal Formalism. 15.2 Conventional Nodal Methods. 15.3 Transverse Integrated Nodal Diffusion Theory Methods. 15.4 Transverse Integrated Nodal Integral Transport Theory Models. 15.5 Transverse Integrated Nodal Discrete Ordinates Method. 15.6 Finite-Element Coarse Mesh Methods. 15.7 Variational Discrete Ordinates Nodal Method. 15.8 Variational Principle for Multigroup Diffusion Theory. 15.9 Single-Channel Spatial Synthesis. 15.10 Multichannel Spatial Synthesis. 15.11 Spectral Synthesis. 16 Space-Time Neutron Kinetics. 16.1 Flux Tilts and Delayed Neutron Holdback. 16.2 Spatially Dependent Point Kinetics. 16.3 Time Integration of the Spatial Neutron Flux Distribution. 16.4 Stability. 16.5 Xenon Spatial Oscillations. 16.6 Stochastic Kinetics. APPENDICES. A Physical Constants and Nuclear Data. B Some Useful Mathematical Formulas. C Step Functions, Delta Functions, and Other Functions. C.1 Introduction. C.2 Properties of the Dirac delta-Function. A. Alternative Representations. B. Properties. C. Derivatives. D Some Properties of Special Functions. E Introduction to Matrices and Matrix Algebra. E.1 Some Definitions. E.2 Matrix Algebra. F Introduction to Laplace Transforms. F.1 Motivation. F.2 "Cookbook" Laplace transforms. Index.
699 citations
Additional excerpts
...65× 10(6) [39] (136)Xe ∼ 1× 10−3 [40] (149)Sm [4....
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TL;DR: The authors derived exact one-dimensional integral equations for the three-body scattering problem by applying the Schmidt method (quasi-particle method), which is more practical than those of Faddeev and has the structure of multi-channel twoparticle Lippmann-Schwinger equations.
608 citations